Analysis of tritium production in a 2 MW liquid-fueled molten salt experimental reactor and its environmental impact  

作　　者：Xiao-Wen Lyu Xiao-BinXia Zhi-Hong Zhang Jun Cai Chang-Qi Chen 

机构地区：[1]Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, China [2]University of Chinese Academy of Sciences, Beijing 100049,China

出　　处：《Nuclear Science and Techniques》2016年第4期7-13,共7页核技术（英文）

摘　　要：Tritium release is one of the most concerning topics in nuclear power plants. Here, the tritium production in a 2 MW liquid-fueled molten salt experimental reactor(TMSR-LF1) was calculated by ORIGEN-S with an updated cross-section library generated by TRITON in SCALE 6.1.3 code system. The results show that the tritium production rate and normalized tritium production rate of TMSR-LF1 are 8.90x10^(11)Bq/day and4.45x10^(11)Bq/(MW day), respectively. The environmental impact of tritium was analyzed via PC-CREAM 08 with an assumed 36 % release rate of tritium referring to the molten salt reactor experiment. During normal operations, the maximum tritium concentration is 1.4 Bq/m^3 under normal condition, and the corresponding individual dose to the public is about 1 μSv/a; under extreme conditions, the maximum concentration and corresponding individual doses are 11.8 Bq/m^3 and 9 μSv/a, respectively.Ingestion is the main exposure pathway and accounts for62 % of the total dose. Of this, 35 % is from organically bound tritium.Tritium release is one of the most concerningtopics in nuclear power plants. Here, the tritium productionin a 2 MW liquid-fueled molten salt experimental reactor（TMSR-LF1） was calculated by ORIGEN-S with anupdated cross-section library generated by TRITON inSCALE 6.1.3 code system. The results show that the tritiumproduction rate and normalized tritium productionrate of TMSR-LF1 are 8.90 ×1011 Bq/day and4.45 × 1011 Bq/（MW day）, respectively. The environmentalimpact of tritium was analyzed via PC-CREAM 08with an assumed 36 % release rate of tritium referring tothe molten salt reactor experiment. During normal operations,the maximum tritium concentration is 1.4 Bq/m3under normal condition, and the corresponding individualdose to the public is about 1 lSv/a; under extreme conditions,the maximum concentration and correspondingindividual doses are 11.8 Bq/m3 and 9 lSv/a, respectively.Ingestion is the main exposure pathway and accounts for62 % of the total dose. Of this, 35 % is from organicallybound tritium.

关 键 词：氚浓度 生产分析 液体燃料 环境影响 熔盐 实验堆 实验反应堆 TRITON 

分 类 号：TL426[核科学技术—核技术及应用]